ML032250101
| ML032250101 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/01/2003 |
| From: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW030063 | |
| Download: ML032250101 (39) | |
Text
xe kn.M Exelon Generation Company, LLC www.exeloncorp.com NucleaT Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 August 1, 2003 BW030063 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457
Subject:
Core Operating Limits Report (COLR) Revisions The purpose of this letter is to transmit revisions to the Braidwood Station, Unit 1 COLR and the Braidwood Station, Unit 2 COLR in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." These revisions of the COLR were recently implemented to increase the COLR limit for the reactor coolant system (RCS) total flow rate from greater than or equal to 380,900 gallons per minute (gpm) to greater than or equal to 386,000 gpm. The RCS total flow rate is being increased to address a core design constraint that 0% of rods experience departure from nucleate boiling for the Locked Rotor event.
If you have any questions regarding this matter, please contact Ms. Kelly Root, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Micha I J. Pacilio Site Vice President Braidwood Station Attachments: : Core Operating Limits Report for Braidwood Unit 1 Cycle 11 (CAD-03-89, Revision 1) : Core Operating Limits Report for Braidwood Unit 2 Cycle 10 (CAC-02-48, Revision 5) cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station 4u1
bcc: NRC Project Manager, NRR - Braidwood Station Office of Nuclear Facility Safety - IDNS Site Vice President - Braidwood Station Regulatory Assurance Manager - Braidwood Station Director - Licensing, Mid-west Regional Operating Group Manager - Licensing, Braidwood and Byron Stations Nuclear Licensing Administrator - Braidwood Station Nuclear Fuel Management - Robert Lee Exelon Document Control Desk Licensing (Hard Copy)
Exelon Document Control Desk Licensing (Electronic Copy)
ATTACHMENT I Core Operating Limits Report for Braidwood Unit 1 Cycle 11
CAD-03-89, Rev. I CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 1 CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP
CAD-03-89, Rev. I Page 2 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to + 10% at 100% RTP 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit I Cycle 11 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).
The Technical Specifications affected by this report are listed below:
SL 2.1.1 Reor Core Safety Limits (SLs)
LCO 3.1.1 Shutdown Margin (SDM)
LCO 3.1.3 Moderator Temperature Coefficient fMTC)
LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion ULmits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 Physics Tests Exceptions - MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN,)
LCO 3.2.3 Axial Flux Difference (AFD)
LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)
LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Techrucal Requirements Manual affected by this report are listed below-.
TRM TLCO 3.1.b Boration Flow Paths - Operating TAM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources - Operating TRM TLCO 3.1.g Position Indication System - Shutdown TRM TLCO 3.1 .h Shutdown Margin (SDM) - MODE 1 and MODE 2 with keNl 21.0 TRM TLCO 3.1.1 Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1 j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exception)
CAD-03-89, Rev. I Page 3 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits are applicable for the entire cycle unless otherwise identified.
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.
2.1 Reactor Core Safety Limits (SLs) (SL 2.1.1) 2.1.1 In Modes I and 2, the combination of Thermal Power, Reactor-Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the lirmits specified In Figure 2.1.1.
680 271ps.
660 2250 psGa La.
UP 0, 640 \00 \_i a,
I-Q C-E a,
> 620 U)
W C11 600 589 0 .2-4 .6 8~~~~~~ 1.22I Froction of Nominal Power Figure 2.1.1:. Reactor Core Limits
CAD-03-89, Rev. I Page 4 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable APD Limits from -18% to +10% at I100% RTP 2.2 SHUTDOWN MARGIN (SDM)
The SDM lirnit for MODES 1, 2,3, and 4 is:
2.2.1 The SDM shall be greater than or equal to 1.3% Aklk (LCOs 3.1.1, 3.1.4, 3.1.5.
3.1.6,3.1.8,3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.1, 3.1-h, and 3.1.j).
The SDM limit for MODE 5 Is:
2.2.2 SDM shall be greater than or equal to 1.3% Ek/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.1 and 3.1.).
2.3 Moderator Ternmerature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOLUARO/HZP-MTC upper limit shall be +1.185 x l0' bkk/PF. -
2.32 The EOLUARO/HFP-MTC bwer limit shall be -4.6 x 10 4Ak/kPF.
2.3.3 The EOUAR01HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak F.
2.3.4 The EOLUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10, AkIkF.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2A Shutdown Bank Insertion Lirnits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with the Bank A greater than or equal to 224 steps, shall be limited In Physical insertion as shown In Figure 2.5.1.
2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.
2.5.3 The control banks shall be operated In sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.
2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:
Park Position (step) Overlap Limit (step) 225 110 226 - 111 227 112 228 113 229 114
CAD-03-89, Rev. I Page 5 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -I 8% to +10% at 100% RTP hgure 2.S1:
Co" Bank Inseaon UmtsVersus Percent FtedThenm I
la (lMEq 161) 0 10 0-
.x 0
0 10 20 30 40 5D 69 70 80 90 100 wwwPo (Pernt)
CAD-03-89, Rev. I Page 6 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP 2.6 Heat Flux Hot Channel Factor (Fn(Z)) (LCO 3.2.1) 2.6.1 FRTP FQ(Z)< x xK (Z) forP<0.5 0.5 FQ(Z) S-- -xK(Z) forP >0.5 where: P = the ratio of THERMAL POWER lo RATED THERMAL POWER Fp = 2.60 K(Z) Is provided InFigure 2.6.1.
2.6.2 W(Z) Values:
a) When PDMS is OPERABLE. WM =1.00000 for all axial points.
b) When PDMS is Inoperable, W(Z is provided in Figures 2.6.2.a through 2.6.2.d.
The normal operation W(Z) values have been determined at bumups of 150, 6000,14000, and 20000 MWD/MTU.
Table 2.6.2 shows the Fco(z) penalty factors that are greater than 2% per 31 Effective Full Power Days. These values shall be used to increase the FWo(z) as per Surveillance Requirement 3.2.1.2. A 2%A penalty factor shall be used at all cycle bumups that are outside the range of Table 2.6.2.
2.6.3 Uncertainty
The uncertainty, UFO, lo be applied o. the Heat Flux Hot Channel Factor Fo(Z) shall be alculated by the following formula UIe = UV. *U, where:
Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable.
(U. Is defined by PDMS when operable.)
U. = Engineering uncertainty faclor = 1.03 2.6.4 PDMS Alarms:
FQ(Z) Warning Setpoint > 2% of Fo(Z) Margin FQ(Z) Alarm Setpoint > 0% of Fo(Z) Margin
CAD-03*89, Rev. I Page 7 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Figure 2.6;1 K(Z) - Normalized F0 (Z) as.a Function of Core Height 1.1 t,,
(0.011.0) l(6.0 1.0) 0.9 1 -r-I.-.-I -I IIII I -
10.924)
~~~~~~~~~(12.(
0.8 - a 0.7 0
N 0.6 _ - - - -_
-a 0.5a 0___LOCALinifing 0.4 - _ - Envel 0.3 - - a - a -
O2 0.1 _
0O 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (f)T TOP
CAD-03-89, Rev. 1 Page 8 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable Al D Limits from -18% o +10% at J00% RTP Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Height MAX W(ZI Feel StokwAoxd hUr I Cycle I1I 0.0 1.0000 020 la00 F~g'e 2.62A 0.4 1t0w 0.60 Sumaroy cI W(7) Function of 150 MWAD/M11J 0.80 (Top ard 1of1am 15% Ex'ck3ded pet WCAP-10216) 1.00 1U000 1.20 lAO 1.60 1.80 1.1 3.2450 200 22D 240 321333 260 2.80 L.2027
&OD 3.00 3.20 1.1836 1.30 3.60 1.1321 3A0 3.17301
.1.3650 4.00 420 1.1345 4.40 4.60 1.1248 4.80 1.1142 125 14026 520 3.0986 1.0983 5.16 1.3096 z
5.80 3.1369 6.00 1.1263 620 1.1339 Z 1.20 I*T' 6.40 1.1416 6.60 1.14S8 6.80 7.CO 3.1620 7.2D 1.1739 7.40 7.60 .1.3894 7.J0 1.1971 1.15 1.2024 8.20 8.60 8.8D 9.0D 32102 9.20 9.40 1.10 9.60 1211 9.80 10.00 10.20 12317 10.40 10.60 10.80 Iuoo 1.0000 1.05 p120 0.00 2.00 4.00 6.00 8.C.0 10.00 12.0O 11.40 1.0=0 CORE HEIGHT (FEET) 11.60 l.0000 11.80 3.0000 12.0D
CAD-03-89, Rev. 1 Page 9of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE I J Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Heigh1 MAA.XW(Z)
Feel N~dctwood"UIt 1cycle Ii 3.0000 020 l.000 Flgwe 262.b 0.40 3.0000 0.60 L.0000 Surnmory d W(D Function at 6000 NMWMIU OWS 1.0000o (Top and Bottom 15%Eaick~ed pef WCAP-102 16) 3.0000 12D 3l000 3I000
)AM0 II 1.60 1.80 2.O0 Z2.2 22D 260 13113 1US91 132634 12413 132273 32003 II I II II 2.80 3m 1.1934 131f44 I
3.40 3.3760 3A0 3.1684 380 3.1408 4.00 3.3515 3.1412 4.20 4.40 4.60 1.3313 3.1190
- I 4.80 1.1079 5m 3.0987 5420 1.0931 3.095 tI 5.0 3.099 5S. 1.13W 6.00 3.1102 6.20 3.3343 6.40 3.3205 6.60 3.1342
- 68. 1.3459 7.00 1.1576 720 3.1698 7.40 3.3181 7.60 1.1933 7.80 1.2031 8.00 1.2121 8.20 1.2171 8.40 3.223 8.60 3.2287 a-so 3.249 9.00 1.2445 9.20 5.2630 9.40 12750 9.60 1.2S8 9.80 1204 0.00 1.2970 10.20 1.3030 10.40 1.0000 10.60 3.0000 10.80 3.000 110 1.000 1120 3.0000 34AO 1.0000 1160 3.0000 11.80 3.0000 12.00 1.0000
CAD-03-89, Rev. I Page IOof 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -1 8% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Umits from -18% to +10% at 100% RTP Height MAX W(Z) feel Brok1w~ood Unil I Cycle I I 0-00 1.0000 0.20 I tIw 2.6.2.c 0>40
&owrmory of W(Z Fumcton ot 1400 MWO/MI OLID 1000 1.0000 (IoP mod Botom 15% Enckoded pmtWCAP-10216) 1.0000 140 1L0000 3.0000 1.60 13009S Am9 1180 200 220 2A0 26O 2.80 33096 1.2769 1.2651 1.2512 1.2422 1I U3. 1.2321 320 120 340 1.2084 3.60 1.202S 3.80 LIM 1.1,902 420 4AO 4.60 1.1120 131734 1.1639 I *1 4.80 1.1544 3.3440
'.340,1
£40 1,401 5.43 520 1.140t 1.3452 6800 1.3538 6.20 3.1704 640 3.33DD 6.60 1.1365 6.80 3.31913 7.00 1.1940 720 7A0 3.3927 7.6 3.195 7.0 8.0 8.20 8.A0 8.60 3.3796 1.16Z7 31.697 L3627 t~577 I I1 680 1.1561 9m 1.1561 920 1.1537 9.4 1.1524 9.60 1.1497 9.80 10.0 1.20S0 1020 1.2360 10.40 1.0000 10.0 10.80 9M00 11.O 2z00 11.20 3.0000 1140 1.0000 11.60 3.0000 MO.80 12.00 1.0000
CAD-03-89, Rev. I Pagc I I of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limils from -1 8% to + 109' at 100% RTP Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Height Fee 1#Oldoodr 1. CyCle 1I 1100 3.0000 Q20 Figme 2.62,d 0.60 3.0000 Survviory of W(Z) Fun~ction of 20000 MWD/MUl Q80 (top ond Bottom 15% Exckxcied pet WCAP..10216)
I00 120 IW000 1.40 leo J.000 1.3s lJO 120 z40 1.2590 2,60 1.2390 2.80 3.0D 3.20. 1.2020 1.30 3.19)0 I4 3.40 3.60 1.1910 3.80 too 1.1892 4.20 4.40 1.1871 4.60 I.IW5 4.80 1.20238 1.25
&aOD 1.2089 6.20 32309 A40 32125 1.2110 4LH1
&60
.80 .2-2~0 z 6.00 1-2334 6.20 1.2431 0 1.2501 Z 1.20 6AO 6.60 1.2545 b.W0 I2563 .R 7.00 1.2512 7.20 3.2491 1.2430
_7.60 1.2311 7.80 8.00 1.2192 3.2061 1.15 I - J. .4-5 J..J....4 I I
4 444..-4 .-i ..I-.-J..
8.20 3.1914 LIMSf 3.3625 3.3644
-LI i1 -i-rii-i rrrv I iri vi-ii -
9.00 1.1640 9.20 1.1313 9.40 1.1702 1.10 9.60 1.2110 9.80 1.2490 10.00 3222
- -I. .-
10.20 1.3142 10.40 3.0000 10.60 3.000 10.80 3.000 I I 11.00 ID=0 1.051 11.20 3.600 O.CDO 2.00 4.00 6.00 8.00 tO.00 12.O0 11.40 I.0OD CORE HEIGHT (FEET) 11.60 3.60000 11.0 1.0000 12.00 3.0000
CAD-03-89, Rev. I Page 12 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to 1J0% at 100% RTI Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Table 2.6.2
- Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor- F'0 (z)
(MWD/MTU) )
495 2.00 839 44A8 1012 5.66 1184 6.58 1356 7.15 1529 7.20 1701 6.97 1874 6A9 2046 5.82 2218 5.10 2563 3.79 2735 3.35 2908 3.10 3080 3.01 3597 3.16 3769 3.09 3942 2.86 4114 2.47 4286 2.01 4459 2.00 Notes:
Linear interpolation Is adequate for Intermediate cycle bumups.
All cycle bumups outside the range of the table shall use a 2% penalty factor for cormpriance with the 3.2.1.2 Surveillance Requirements.
CAD403689: Rev. I Page 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable forPDMS Inoperabie AFD Limits from -18% to +1O% at I00% RTP 2.7 Nuclear EnthalPy Rise Hot Channel Factor (ETaH) (LCO 3.2.2) 2.7.1 F^H S FZTP[ 1 .0 + PFX,,(1.0 - P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FZ' = 1.70 PFK = 0.3 2.7.2 Uncertainty when PDMS Is inoperable The uncertainty, UF&H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FHN shall be calculated by the following formula:
UFW4 = UF where:
UxF~= Base F%4 measurement uncertainty =1.04 2.7.3 PDMS Alarms:
F'4H Warning Setpoint a2% dof Fj Margin F ' Alarm Setpoint 2 0% of FNaH Margin 2.8 Axial Flux Difference (AFD) (LCO 32.3) 2.8.1 When PDMS is Inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.
2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
2.9 Deparlure from Nucleate Boilino Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRApsL 1.536 The Axdal Power Shape Umiting DNBR (DNBRpsL) Is applicable with THERMAL POWER > 50%/* RTP when PDMS Is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint > 2% of DNBR Margin DNBR Alarm Setpoint > 0% of DNBR Margin
CAD-03-89, Rev. I Page 14 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I Applicable for PDMS Inoperable AFD limits from -1 8% to + 10% at 100% RTP Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Applicable for PDMS Inoperable AFD Umits from -18% to +10% at 100% RTP Mal FIlux Uffferermx Units vWth
-PONVS Inoperbl 120 0200 00-I-.180 6(
-i~p allr-- oep W0 W0 40 20 -10 0 10 20 30 40 50 A)XX fUX OEffERB0i4(0/4
CAU-l3-bsy. Kev. I Page 15 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Linits from -18% to +10% at 100% RTP 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip selpoint K, shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpolnt T, coefficient K2 shall be equal to 0.0297/ eF.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient 43 shall be equal to 0.00181 / psig.
2.10.4 The nominal T.,at RTP (indicated) r shall be less than or equal to 588.0 "F.
2.10.5 The nominal RCS operating pressure (indicated) P` shall be equal to 2235 psig.
2.10.6 The measured reactor vessel AT leadtlag lime constant sr shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant a2 shall be equal to 3 se.
2.10.8 The measured reactor vessel AT lag time constant ? 3 shall be less than or equal to 2 seec 2.10.9 The measured reactor vessel average temperature lead/lag time constant 4 shall be equal 1o 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant Ts shall be equal to 4 sec.
2.10.11. The measured reactor vessel average temperature lag time constant ai shall be-...
less than or equal 1 2 sec.
2.10.12 The 1,(Al) "positive" breakpoint shall be +10/e AI.
2.10.13 The It (Al) "negative' breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positive" slope shall be +3.47% 1% Al.
2.10.15 The f1 (A negative slope shall be -2.61% 1% Al.
CAD-03-89. Rev. I Page 16 of 17 CORE OPERATING IUMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -8% to +10% at 100% RTP 2.11 Reactor Trip System (RTS) InsIrumentation (LCO 3.3.1) -Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip selpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint T9 rate/lag coefficient Ks shall be equal to 0.02 / OF for increasing T...
2.11.3 The Overpower AT reactor trip setpoint T,, rate/lag coefficient K5 shall be equal to 0 'F for decreasing T, ,
2.11.4 The Overpower AT reactor trip setpolnt Tao heatup coefficient KG shall be equal to 0.00245 / °F when T > To.
2.11.5 The Overpower AT reactor trip setpolnt T,, heatup coefficient Ki shall be equal to0/'FwhenTSTo.
2.11.6 The nominal T, at RTP (indicated) T" shall be less than or equal to 588.0 eF 2.11.7 The measured reactor vessel AT lead/lag time constant so shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant t 2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant r3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant -re shafl be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant a7 -
shall be equal to 10 sec.
2.11.12 The f2 tAl) positive' breakpoint shall be 0 for all Al.
2.11.13 The f2 (Al) negatives breakpoint shall be 0 for all Al.
2.11.14 The f2 (Al) positivde slope shall be 0 for aft Al.
2.11.15 The f2 (Al) "negativeW slope shall be 0 for all Al.
CAD-03-89, Rev. I Page 17 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I
- Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP 2.12 Reactor Coolant System (RCS) Pressure, Temperature. and Flow Departure from Nucleate Boilina (DNB) Limits (LCO 3A.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psIg.
2.12.2 The RCS average temperature (T.) shall be less than or equal to 593.1 "F.
2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 1701 ppm (LCO 3.9.1).
2.132 To maintain keff 5 0.987 with ell shutdown and control rods fully withdrawn In MODES 3.4, or 5 (TRM 3.1.g Required Action B.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to:
a) 1733 ppm prior to Initial criticality.
b) 1979 ppm at all other times In core life.
ATTACHMENT 1 Core Operating Limits Report
- for Braidwood Unit 2 Cycle 10
CAC-02-48 Rev. 5 >
CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 2 CYCLE 10
CAC-02-48, Rev. 5 PageI of i7 CORE OPERATING LlMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 10 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (iTS).
The Technical Specifications affected by this report are listed below:
SL 2.1.1 Reactor Core Safety Limits (SLs)
LCO 3.1.1 Shutdown Margin (SDM)
LCO 3.1.3 Moderator Temperature Coefficient (MTC)
LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 Physics Tests Exceptions - MODE 2 LCO 3.2.1 Heat Flux Not Channel Factor (Fo(Z))
LCO 3:2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN,.)
LCO 3-2.3 Axial Flux Difference (AFD)
LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
LCO 3.3.1 Reactor Trip System (RTS) Instrunentation LCO 3.3.9 Boron Dilution Protection System (BDPS)
LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO .3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below TRM TLCO 3.1.b Boration Flow Paths - Operating TRM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources - Operating TRM TLCO 3.1.g Position Indication System - Shutdown TRM TLCO 3.1.h Shutdown Margin (SDM) - MODE 1and MODE 2 with keff >1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1tj Shutdown and Control Rods TRM TLCO 3-1.k Position Indication System - Shutdown (Special Test Exception)
CAC-02-48 , Rev. 5 Page 2 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits are applicable for the entire cycle unless otherwise identified.
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.
2.1 Reactor Core Safety Limits (SLs) (S1 2.1.1) 2.1.1 In Modes 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shalg not exceed the imits specified in Figure 2.1.1.
Sao 247J pmi S650 Lj-.
C70 i..
0-E.
U) 6200 581 Frocdion of lNomiol Power Figure 2.1.1: Reactor Core Limits
CAC-02-4 8, Rev. 5 Page 3 of 17 CORE OPERATING LIMITS REPORTIcOLR) for BRAJDWOOD UNIT 2 CYCLE 10 2.2 Shutdown Marmin (SDM)
The SDM limit for MODES 1, 2, 3. and 4 is:
2.2.1 The SDM shall be greater than or equal to 1.3%/6 Akfk (LCOs 3.1.1. 3.1.4, 3.1.5, 3.1.6,3.1.8,3.3.9; TRM TLCOs 3.1.b, 3.1.d. 3.1.f, 3.1.h, and 3.1.]).
The SDM limit for MODE 5 is:
2.2.2 SDM shag be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1j).
2.3 ModeratorTemperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOIJAROAHZP-MTC upper limit shal be +2.57 x 10r Ak/kIF.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 1 Df Ak/klF.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shag be 47 x 1IJ Ak/k/OF.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10 k/k1F. ~
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1. All shutdown banks shall be fully withdrawn to at least 224 steps. . ..
2.5 Control Bank Insertion Limits (LC0 3.1.6) 2.5.1 The control banks, with the Bank A greater than or equal to 224 steps, shall be lirmied in physical insertion as shown h Figure 2.5.1.
2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.
2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shag be sequenced in reverse order upon insertion.
5 CAC-02-48, Rev.
Page 4 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE IO 2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:
Park Position (step) Overlap Lnnit (step) 225 -
t10
_ 226 227 228 11i 112 113 229 I 114
CAC-V2-48, iKev. > Pagc5 of 17 CORE OPERATINGIUMITSREPORT (COLR)forBRAIDWOODUNIT22 CYCLE 10
- Figre 251::
Cor Bank Isrlon Unts Verss Percent PWd Thenal
-Power 224 (nV 22 180 C
'Su18D (1% 161)
CL a) 0 0
. 0 C
0 40-0 10 20 30 . 40 SD 6) 70 OD 9D 100 RelveP w e)
CAC-02-48, Yev. -
Page 6 of 17 CORE OPERATING LIMITS REPORT (COLA) for BRAIDWOOD UNIT 2 CYCLE 10 2.6 Heat Flux Hot Channel Factor Fool (LCO 3.2.1) 2.6.1 pRTP FQ(Z)< o-5 xK(Z) forP50.5 FQ(Z) <- Q xK(Z) forP>O.5 P
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FT = 2.60 K(Z) is provided in Figure 2.6.1.
2.6.2 W(Z) Values:
a) When PDMS is OPERABLE, W(Z) = 1.00000 for all axial points.
b) When PDMS is Inoperable. W(Z) is provided in Figukes 2.6.2.a through 2.6.2.d.
The normal operation W(Z) values have been determined at bumups of 150, 6000.14000. and 20000 MWDIMTU.
Table 2.6.2 shows the Fca(z) penalty factors that are greater than 2ND per 31 Effective Full Power Days. These values shaD be used to Increase the Fwa(z) as per Surveillance Requirement 3.2.1.2. A 2%/iS penalty factor shall be used at an cycle bumups that are outside the range of Table 2.6.2.
2.6.3 Uncertainty-The uncertainty, UFO, to be applied to the Heat Fkux Hot Channel Factor Fa(Z) shall be calculated by the following formula U, 0 = U.,, * .,
where:
Uq = Base FO measurement uncertainty = 1.05 when PDMS is inoperable.
(Uq is defined by PDMS when operable.)
U. = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
FC(Z) Warning Setpoint > 2% of Fo(Z) Margin FC(Z) Alarm Setpoint > 0% of FO(Z) Margin
CAC-02-48, Rev. 5 Page 7 of 17 CORE OPERATING LIMITS REPORT (couR) for BRAIDWOOD UNIT 2 CYCLE 10
-~~~~~~~~~~~~
Figure 2.6.1 K(Z) - Normalized Fa(Z) as a Function of Core Height 0
0 Z
0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) ,TOP
CAC-0248, Rev. 5 Page 8 of J7 CORE OPERATING LIMITS REPORT (COlR) for BRAIDWOOD UNIT 2 CYCLE I 0 Height MAXWa)
Feet Stoidwood Unl 2 Cycle 10 0.0D 1.0000 0.20 Flgur 26.62 Q40 1.0000 0.60 SumTmwy ot W(a) Fundon at lSO MWK/VMU C8o (rop ond 1ot*om IS% fxcbded pet WCAP- 10216) 1.CO 3.00WD 1.20 1.40 1.00W 1.60 lOW 1.35 1.80 8.1882 1.18S2 200 2.20 1.1684 2.40 3.3589 2.60 1.1489 2z0 1.1399 ao. 3.1304 3.20 3.1228 1.30 314 16O 1.1333 380 400 1340t a.20 1.1445 44D 1.1472 4.60 1.3479 V I 4.80 1.1486 1.25 500 1.1473
&2D 1.1450 640 1.1437 a60 1.1433 5.8 1.1548 6.CO 1.1656 6.20 1.1803 6.4D 1.1920 6.60 1.2037 6.80 1.2125 7.OD 1.2203 720 12261 7.40 1.2338 7.60 1.236 7AO 1.2436 1.15 8.00 1.2475 B.20 1.2463 8S. 1.247S 860 1.2473 8.80 1.2419 9.0D 1.2536 9.20 9AO 1.2545 1.10 9.60 1.2531 9.80 1.2484 10.00 12470 10.20 1.2530 10.4O IJOW 8.0000 10.60 1.0000 10.80 11.00 1.Cis 1.0000 11.20 0.0D 2.00 4.00 6.00 8.00 t0.00 12.00 1 eoo IAdO 3.0000 11.60 1.0000 CORE HEIGHT (FEET)
MSD 1.0000 1ZO
CAC-02-48, Rev. 5 Page90of ]7 CORE OPERATING LTMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE J0 HdV W3 War)
Fee. Bldd.cUrfl 2 Cyde 10 0.00 3.0000 0.20 1.0000 Flfe2A2.b 040 5.0000 0.60 I.00o0 Suvnray dW() Furacncgi60D MADMI U 0.8o 3.00o0 CcprdBdtclm 15% Exedubdcjer WCP-0 3216) 1.00 3.0o0 1.20 1.00D 1.40 I.0 1IS64 l10 l.000 1.35 1.80 1.2t82 ._
2.eo 2.20 1.236n t _ _
2.40 1.21_3 2.60 1.2079 2.80 MM96 3.20 1.791 1.30 3.60 -,GM
,eo O1O1547
.ZOD 1-3470 4.20 1-:333 4.40 I' 303 4.80 3.127 12 5.8 1.0O3 0
-&OD L)"?R 6.00 3.0313 640 .3.1131m 6.60 12332 6.80 10.00 1.3354
).ecoo ~w 7.00 I' 457 3ADo :.-3oo6nD 7.20 11.40 3.3541 1.1OR6HIGT 40 60 FET
.0 OOO 10 7.60 3.I.6I4 7.60 3.17671 8.20 335 SAO0 1.3759 8.60 L3.37 8.80 3.1796 9.00 1.1330 9.20 1.37p5 1.30 9.40 3.179M 9.60 3.1949 9.80 1.2030 F 10.0 J.2097 10.20 32135-------
10.60 1l000 31.00 1.000 o.oo 2.00 4.00 s.oo a.oo 10.Oo 12.00 11.20 3.0000 11.40 1.000 CORE HEIGHT (FEET) 11.60 3.0A0 12.0 3.0000
CAC-0248, Rev: 5 Page 10 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 H1p M Wa)
Feet Blddt7Urd32Cyde 10 0.00 1.0000 D.20 I.oo00 Fi9e2.2.c 0.40 L.0ooO 0.60 1.000 Sutrray et W(Z)Fuic~m d 14000 MvNOP U 0.80 1.0000 (rcpid Beffcn 15% ExduXedw WCAP-10216) 000o L.OD 7.20 1.0000 1.40 .000W 1.60 1.000D L.80 1.3766 2.00 13572 7.20 1.3321 2.40 1.310t Z60 3.293I z28 3.276 3.00 1.2632 3.20 1.2467 3.40 1.2318 3b60 1.2140 3.0 13.2043
.1 _.1 I
4.0D 1.1947 4.20 3.1834 1.1721 I..1 4.4D 4hD 1.1609 4.80 1.1477 5.00 3.1341 I 1.1314 A -I 5.20 I1 I 5.40 5.6b s58 6.OO 6.20 6.4) 3.1237 1.325 1.122.
1.1236 1.1324 1.1382 t I.i I
6.60 1.1427 6.80 1.1449 I.I I I I. I I I 7M 1.1464 f 41 13 7.20 1.1476 7.40 3.1464 7.60 1.1396 r7.8D * - 1.357. I 8.OO 1.1306
&20 1.1207 i-II I 1.3 131 8.40 8.60 8.80 9.0D 1.1073 1.1034 3.1050 I I: It 1 9.20 1.1017 9.40 1.1133 9.60 1.1139 9.80 3.12S5 tOO 1.1593 3020 1.3890 10.40 3.0000 10.60 1.000 30.80 3.0000 l1.00 I.0000 1120 1.0000 11.40 1.000 11.60 1.000D 11.80 1.0o0 12.OD 1.000D
CAC-02-4S, Rev. 5 Page IIof 17 CORE OPERATING LlMlTS REPORT (CoLR) for BRAIDWOOD UNIT 2 CYCLE Io Hvt mkxw~z)
Feel Brdd..dUrit 2 Cyde 0 a0.0 130000 Q20 Figpxe26.2.d 0.40 1.8000 0.60 1.8000D Surrroy diW(Z)Ftrdlmn d 2000 &ROMrU 0.80 1cpid~cila Sn1% ExduxbpsWCAP-1 0216) 1.00 L.0000 120 1.80000 VAD I.8000 1.CODD I.C00D 1.60 I 2JO 1.25t3 2.20 1.7317 2AD 1.2124 2.60 1.1966 2.a0 1.1SS3 3.00 3.20 1.170D 3A0 1.161 3.60 1.1670
.00 1.1657 I I 420 4A0 1.732 1.1842 1.1914 1.1969 I I t I I.
5.00 480 5430 12 1.2004 I I1 I 5.80 360D 6.20 6Ao
&.60 1.2165 1.22S0 1.2374 12417 fI 1
_I I
12433 1243?
7.20 1.23S7 740 SSOD 1 2326 7.0 am 122216
.1 7.80 1 6 8.00 1,.1955
-1 1.1732 8.40 t.1633 8.60 8.80 9.CO 1.1475 1.1435 1.1410 I.I I Ii I 9.2D 9.40 1.1833 IJ1349 9.60 1.1151 980 1.2267 10.00 1640 10.20 1.3048 10.0 I.0000 10.60 .0000 108o 1.0000 11.O0 l.OOOD
- 1. 1.
I I LL I I 11.20 1.000M 1U.40 I.OCOD 11.60 l.0000 11.80 I.OOOD 12.00 1.0000
CAC-02-48, Rev. 5 Page 12 of 17 CORE OPERATING LIMITS REPORT (CoLR) for BRAIDWOOD UNIT 2 CYCLE 10 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penally Factor - Fco(z)
(MWD/MTlU) %)
2038 2.00 3068 3.13 3239 3.24 3411 3.30___
3583 3.28 3754 3.18 3926 3_00 4612 _ 2.04 10791 2.00 10963 2.08 11477 2.32 116-49 2.38 11821 2.41 11992 2.46 12164 2.47 42336 2-45 12507 -- - 2.41 12679 2.27 12850 : 2.00 Notes- .
LUnear Interpolation is adequate for intermediate cycle bumups.
All cycle burnups outsidd the range of the table shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.
CAC.02.48, Rev. S Page 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.7 Nuclear Enthaloy Rise Hot Channel Factor (F!M) (LCO 3.2.2) 2.7.1 FN. S F^,1.O + PFH(1 .0 - P)j where: P = the ratio of THERMAL POWER to RATED THERMAL POWER
- ~~~Fr,"HP 1.70 PF = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFaH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor Fm shall be calculated by the following formula:
UFdH = UF',.m where:
U&*,,= Base F'H measurement uncertainty =1.04 2.7.3 PDMS Alarms:
FKH Warning Selpoint 2 2% o F" 6 Margin F:, Alarm Setpoint 2 0% of FON Margin 2.8 Axial Flux Dilference (AFDI (LCO 3.2.3) 2.8.1 When PDMS Is Inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided In Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever Is more conservative.
2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
2.9 Departure from Nucleate Boiling Ratio :DNBR) (LCO 3.2.5) 2.9.1 DNBRAmPS 21.536 The Axial Power Shape Limiting DNBR fDNBRpW is applicable with THERMAL POWER 2 50% RTP when PDUS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint 2Ž2% of DNBR Margin DNBR Alarm Selpoint Ž0%2 of DNBR Margin
CAC-o2- 4 8 , Rev. 5 Page 14of17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE 10 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power
CAC 4 8 , Rev. 5 a 1 Page 15 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.10 Reactor rno System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K, shall be equal to 1.325-2.10.2 The Overtemperature AT reactor trip seipoint Tw coefficient K2 shall be equal to 0.0297//F.
2.10.3 The Overiemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 /psi.
2.10.4 The nominal T., at RTP (indicated) T' shall be less than or equal to 588.0 -F.
2.10.5 The nominal RCS operating pressure (indicated) Pi shall be equal to 2235 psig.
2.10.6 The measured reactor vessel AT lead~ag time constant r, shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant r2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant r3shal be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant r4 shall be equal to 33 sec.
~2.10.10 The measured reactor vessel average temperature leadtlag tirme constant T.
shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant Ts shall be less than or equal to 2 sec.
2.10.12 The f1 (Al) 'positive breakpoint shag be +10/ Al.
2.10.13 The 1s (A1) 'negative' breakpoint shall be -18% Al.
2.10.14 The f1(Al) positives slope shall be +3.47% 1 % Al.
2.10.15 The f (Al) 'negative slope shag be -2.61%I % Al.
4 5 CAC S, Rev.
_.CAC-)2-48, Rev. 5 Page 166f1 Pg of 17 UNIT 2 CYCLE I0 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD
- Overpower AT Setpoint 2.11 Reactor TriP Svstem fATS) Instrumentation (LCO 3.3.1-)
Parameter Values equal to 1.072.
2.11.1 The Overpower AT reactor trip setpoint K4 shall be Ks shall be equal 2.11.2 The Overpower AT reactor trip setpoint T>, rate/lag coefficient to 0.021 °F for increasing T, Ks shall be equal 2.11.3 The OverpowerAT reactor trip setpoint T., ratellag coefficient to 01 OF for decreasing T..
K shall be equal 2.11.4 The Overpower AT reactor trip setpoint T,,heatup coefficient 6 to 0.002451 'F when T > T.
K shall be equal 2.11.5 The Overpower AT reactor trip setpoint T9heatup coefficient 6 toO IF when T:5 T.
or equal to 588.0 °F.
2.11.6 The nominal T.> at RTP (Indicated) T' shall be less than t, shall be equal to 2.11.7 The measured reactor vessel AT lead/lag time constant 8 see.
x shall be equal to 2.11.8 The measured reactor vessel AT leadlag tire constant 2 3 sec.
be less than or equal 2.11.9 The measured reactor vessel AT lag time constant vr shall to 2 sec.
time constant 'sshall fU 2.11.10 The measured reactor vessel average temperaturelag less than or equal to 2 sec.
rate/lag time constant s7 2.11.11 The measured reactor vessel average temperature shall be equal to 10 sec.
2.11.12 The 12 (A) 'posftive' breakpoint shall be 0 for all Al.
2.11.13 The f2(Al 'negative breakpoint shall be 0 for all Al.
2.11.14 The 12 (A) 'positivf' slope shall be 0 for all Al.
2.11.15 The 2(Al) 'negative slope shall be 0 for all Al.
CAC-02-48 Rev. 5 Page 17 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.12 Reactor Coolant System (RCS) Pressure. Temperature, and Flow Departure from Nucleate Boilina (DNB) Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.
2.12.2 The RCS average temperature (T..) shall be less than or equal to 593.1 -F.
2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 1733 ppm (LCO 3.9.1).
2.13.2 To maintain keff < 0.987 with all shutdown and control rods fully withdrawn in MODES 3.4, or 5 (TRM 31 .g Required Action B.2 and TRM TLCO 3.1 .k.2), the Reactor Coolant System boron concentration shall be greater than or equal to:
- a. 1778 ppm prior to initial criticality
- b. 1990 ppm at all other times In core life.